Technology Development of a High-Capacity High-Assay Low-Enriched Uranium Transportation Concept

Elmar Eidelpes, Josh Jarrell, Denise Bertsch, Robert Hall, William Marshall, Brian Hom, Harold Adkins

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

This paper discusses the technology development efforts that led to the development of a high-capacity high-assay low-enriched uranium (HALEU) transportation concept. In 2018, the Department of Energy tasked Idaho National Laboratory to investigate strategies to transport large quantities of HALEU. To complete this task, Idaho National Laboratory collaborated with Pacific Northwest National Laboratory and Oak Ridge National Laboratory. One of the project outcomes was a transportation concept of five individual Type B packages transported on a single legal-weight truck. The total payload capacity of this concept is 1,881 kg (4,149 lb) of HALEU in the form of uranium dioxide (UO2) powder. It utilizes an existing Type B packaging design carrying a novel fuel basket design with an incorporated flux trap. The basket can be loaded with 18 individual fuel canisters. The research collaboration investigated the U.S. certification potential of this concept, which included evaluating criticality safety, radiological safety, thermal safety, structural integrity, and confinement under hypothetical accident scenarios of transport. The results of these evaluations demonstrated a promising potential for the U.S. certification of this concept. Eventually, these efforts led to the pursuance and issuance of a U.S. patent, thus protecting the associated intellectual property. Current short-term goals include making this intellectual property available to private industry partners for licensing, directly supporting Department of Energy’s objectives of accelerating the commercialization of national-laboratory-generated intellectual property. Long-term research goals would include exploring the feasibility of transporting other uranium chemical forms (e.g., UF4) or refining operational procedures to load or unload the packagings.

Original languageEnglish
Title of host publicationPacific Basin Nuclear Conference, PBNC 2024
PublisherAmerican Nuclear Society
Pages220-229
Number of pages10
ISBN (Electronic)9798331307653
DOIs
StatePublished - 2024
Event2024 Pacific Basin Nuclear Conference, PBNC 2024 - Idaho Falls, United States
Duration: Oct 7 2024Oct 10 2024

Publication series

NamePacific Basin Nuclear Conference, PBNC 2024

Conference

Conference2024 Pacific Basin Nuclear Conference, PBNC 2024
Country/TerritoryUnited States
CityIdaho Falls
Period10/7/2410/10/24

Funding

This material is based on work supported by the DOE Office of Nuclear Technology Research and Development (NE-4) funding [DE-AC07-05ID14517]. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U. S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof. The authors gratefully acknowledge the support to this project provided by ORNL staff, specifically Bret D. Brickner and Rose A. Montgomery, along with former ORNL staff member John M. Scaglione. Further, the authors would like to express their gratitude to NAC International for providing information to support this research.

FundersFunder number
Oak Ridge National Laboratory
U. S. Government
DOE Office of Nuclear Technology Research and DevelopmentDE-AC07-05ID14517, NE-4

    Keywords

    • advanced reactor fuel
    • High-assay low-enriched uranium
    • transportation

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